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National Repository of Grey Literature 2 records found  Search took 0.01 seconds. 
THE EFFECTS OF HIGH TEMPERATURE HELIUM GAS ON THE FRACTURE BEHAVIOUR OF ODS MA957
 Rozumová, L. ; Hojná, A. ; Kalivodová, J. ; Bublíková, P. ; Hadraba, Hynek ; Di Gabriele, F.
Oxide-dispersion-strengthened steel (ODS) MA957 has been studied as a candidate material for Tritium Breeding Blanket for fusion reactors with helium coolant, where temperatures 250-650 degrees C are expected. Helium is one of type as primary coolant in High Temperature Reactor and Gas Cooled Fast Reactor with working temperature 500-1000 degrees C. \n\nThis work presents results of the study of behaviour of ODS (MA957) under influence of high temperature helium environment. Microstructure of the material and the interaction with He was investigated. The average exposure temperature was held at 720 degrees C. Subsequently, the surface changes were determined. Impact testing and material surfaces were studied in detail by means of SEM and TEM microscopy. It is essential to understand the He effect on microstructure and mechanical properties of structural materials since the He embrittlement in TBB may be significant.
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Embrittlement of ferritic 14%Cr ODS steel in air and in Pb/Pb-Bi coolants at elevated temperatures
 Hadraba, Hynek ; Dlouhý, Ivo ; Hojná, A. ; Di Gabriele, F.
The work was focused to describing influence of long-time high-temperature exposition of the ferritic 14%Cr ODS steel to the liquid Pb and Pb-Bi metals environments. The steel was during exposition in the liquid Pb and Pb-Bi at 600°C and 550°C respectively depleted from Cr and Ti formed with Pb and Bi the surface oxide scale. In addition the isothermal ageing of the steel at 650°C caused precipitates coarsening and porosity development by dislocation annealing in the bulk of the steel. Tensile and impact bend tests reveals outstanding embrittlement of the isothermally aged ODS steel and the steel after exposition to the liquid Pb and Pb-Bi compared with the steel in as-received state.
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